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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept TXX-9026, Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan1990-08-13013 August 1990 Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0151990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violation a Noted in Insp Repts 50-445/90-03 & 50-446/90-03.Corrective Actions: Groundwater Calculations Completed & Engineering Personnel Reminded of Procedural Requirements 1990-09-04
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.0&tPME.STW985 CovisS4 Peter B. Bloch, Esquire Dr. Kenneth A. McCollom Administrative Judge Chairman 1107 West Knapp Atomic Safety and Licensing 74075 1 Board Stillwater, Oklahoma U.S. Nuclear Regulatory Commission Elizabeth B. Johnson Washington, D.C. 20555 Oak Ridge National Laboratory P.O. Box X, Building 3500 Dr. Walter H. Jordan Oak Ridge, TenneESee 37830 881 West Outer Drive Oak Ridge, Tennessee 37830 Re Texas Utilities Electric Company, et al.
Docket Nos. 50-445-OL and 50-446-OL
Dear Administrative Judges:
Enclosed herewith please find Applicants' ninth submission in response to the Board's request of August 12, 1987, for copies of Applicants' response to "Notices of violation" and "Notices of Deviations" issued by the NRC Staff. The enclosed responses cover the period of April 29, 1988 to May 27, 1988.
Respectfully submitted, A
M George L. Edgar Enclosures cc: Service List i
8806140147 880606 N ,$ 0 3 PDR ADOCK 05000445 V G PDR
N EE log # TXX-88449 File # 10130 r C IR 86-26 7t/ ELECTRIC Ref.#$CN2 01 w nne c. cm.a May 16, 1988 em.<,>< > ar new.,
U. S. Nuclear Regulatory Commission Attn
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-146 INSPECTION REPORT N05. 50-445/86-26; 50-446/86-22 REVISED RESPONSE TO NOTICE OF VIOLATION (N0V) ITEM A (445/8626-V-02)
REF: TV Electric Letter TXX-7120 from W. G. Counsil to NRC dated December 31, 1987 Gentlemen:
The referenced letter provided our revised response to Notice of Violation item A (445/8626-V-02). In that response we stated that the Unit I walkdown for pulling aids per CPE-SWEC-FVM-EE/ME/IC/CS-90 would be completed in order to correct this finding. As a result of activities completed in December 1987 and other installation practices, the walkdowns need not be performed for this issue. Our res)onse to Notice of Vi,olation 445/8626-V-02 is hereby revised to reflect these clanges and to update the status of our revision to specification 2323-ES-100.
Where revised res)onses are provided, the revised sections are denoted by a revision bar in tie right margin.
Very truly yours, W. G. Counsil By: .L %
vice President, Nuclear Engineering RDD/grr c-Mr. R. D. Martin, Regivn IV Resident inspectors, CPSES (3) 400 North Ohve Street LB 81 Dallas. Toses bal
. Attachment to TXX-88449 May 16, 1988
. Page 1 of 2
. NOTICE OF VIOLATION ITEM A (445/8626-V-02)
A. Criterion V of Appendix B to 10 CFR Part 50, as implemented by the TUGC0 Quality Assurance Plan (QAP), Section 5.0, Revision 3, dated July 31, 1984, requires that activities affecting quality shall be prescribed by and accomplished in accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances.
Paragraph 3.1.2.e of TUGC0 Procedure Ql-QP-11.3-40, Revision 14, dated January 9,1984, states, in part, "Verify that ... all cable pulling aids have been removed (i.e., fish tape, tape rope, etc.)."
Paragraph 3.1.1.2.c of the above procedure, Revision 18, dated May 18, 1984, states, "Verify that ... pulling aids (i.e., rollers, fish tape, tag rope) have been removed from raceway."
Contrary to the above, TUGC0 inspectors performing post construction inspections failed to identify cable pulling ropes remaining in Class IE conduit C12018896 and Class 1E cable tray T130ACG57 located in the Unit I reactor building and auxiliary building, respectively (445/8626-V-02).
REVISED RESPONSE T0 ITEM A (445/8626-V-02)
TV Electric accepts the alleged violation and the requested information follows:
- 1. Reason for Violation Regarding cable tray T130ACG57, construction procedures controlling cable pulling activities performed subsequent to QC acceptance of raceway systems did not require QC reverification of pulli,1g aid removal.
Regarding conduit C12018896, Revisicn 14 of Ql-QF-11.3-40 in effect at the time of post construction inspection required QC inspectors to identify visible pulling aids but did not require the removal of junction box, pull box or conduit covers to verify that pulling aids had been removed.
- 2. Corrective Steps Taken and Results Achieved Nonconformance Report (NCR) E-86-1038835 and Construction Deficiency Report (CDR) 87-4746EC (previously NCR E-86-103981) were issued to address 1 pull ropes in conduit C12018896 and cable tray T130ACG57, respectively.
Both documents have been Jispositioned "rework" by directing the removal of the pull ropes. NCR E-86-1038835 has been closed.
Corrective Action Request (CAR) 87-59 has been initiated which will address the generic implictions of this violation and will define appropriate corrective actions.
Attachment to TXX-88449
/ May 16, 1988 Page 2 of 2
- 3. Corrective Steps Which Will be Taken to Avoid Further Violations On July 24. 1987, Procedure eel-7, "Cable Pulling," was revised to require removal of all pullina aids (pull ropes, fish tape, etc.) after cable pulls into covered cable trays or conduit are completed. After further evaluation it was determined that, with certain restrictions, it is acceptable to leave pull ropes in conduit runs. On October 28, 1987, Design Change Authorization (OCA) 58763, Rev. O to 2323-ES-100 was issued providing this allowance and detailing the restrictions.
A OCA to revise 2323-ES-100 has been issued which emphasizes that pull l ropes are to be left in conduits only when their removal may result in damage to adjacent cables, Quality Instruction Ql-QP-II.3-40, "Post Construction Inspection of Electrical Equipment and Raceways," has been deleted. In process inspections for pulling aids are performed in accordance with procedures NOA-3.09-3.02, "Electrical Raceway-Cable Tray," and NQA-3.09-3.03, "Electrical / Raceway Conduit Procedure." These procedures provide inspection criteria commensurate with the requir6nents contained in Specification 2323-ES-100.
On November 6, 1987, the Director of Construction issued a directive requiring that all visible metal fish tapes be removed from Unit I and Unit 2 raceways, or if removal was not feasible an NCR was to b written.
This action was reported complete on December 18, 1987. The completion of this activity and inspection attributes which require that conduits be free of foreign debris prior to the installation of electrical penetration seals completes our corrective action for this finding.
- 4. Date When Full Compliance Will be Achieved Full compliance has been achieved.
, P. Log # TXX-88450 l =. .= File # 10130 C C 1R 87-16 C R"I. # C 2 01 I
I,I",$d%,1, May 16, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INSPECTION REPORT N05. 50-445/87-16; 50-446/87-13 REVISEDRESPONSETONOTICEOFVIOLATION(NOV)
ITEM C (445/8716-V-12)
REF: TV Electric letter TXX-88221 from W. G. Counsil to NRC dated March 15, 1988 Gentlemen:
The referenced letter provided our updated response to Notice of Violation item C (445/8716-V-12). In that response we stated that by May 15, 1988, a program would be established whereby a team would observe ongoing work to assess whether the activities were within the scope of applicable work documents, and whether damage was occurring to equipment in the area. We have determined that this observation of ongoing work should be incorporated into our existing Quality Assurance surveillance program. As result of the surveillance activity, additional sampling is not required. Our response has been revised accordingly. Our response has also been revised to reference an October 16, 1987 Vice-Presidential Directive to engineering and construction personnel rather than the previously discussed NE0 policy statement. The Vice-Presidential Directive was considered to be more appropriate for emphasizing requirements to perform work only within the scope of authorized documents. Other sections of our response have been revised to indicate actions completed.
Where revised responses are provided, the revised sections are denoted by a avision bar in the right margin.
Very truly yours, U. G. Counsil By: 4- O .
Jbhn W. Beck Vice President, Nuclear Engineering i
400 North Ohve Street LB&l Dalk. (ese 73.'01
o.
t-ROD /grr c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) t
s Attachment to TXX-88450 May 16, 1988 Page 1 of 3 NOTICE OF VIOLATION IfEHTTM787f6 V-T2)
C. Criterion (VI of Appendix 8 to 10CFR Part 50, as implemented by Section 16.0, Rev.sion 0, of the TV E,lectric QA Plan, states in part, "Measures shall be established to assure that conditions adverse to quality, such as failures malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition..."
TV Electric, in response to Corrective Action Report (CAR) 65X, which identified a missing cotter pin as a Construction Deficiency, established the Hardware Validation Program (HVP) for safety-related pipe supports.
Included in this program is a required verification that locking devices are present and correctly installed.
Contrary to the above, the sway strut rear bracket load pin on safety-related pipe support CC-1-295-006-C53R, Revision 4, was observed on August 21, 1987, to have two missing cotter pins although this support had been reworked by craft and accepted by QC in accordance with the HVP (445/8716-V-12).
UPDATED RESPONSE TO VIOLATION ITEMTTM78716-V-12)
TV Electric agrees with the alleged violation and the requested infonnation follows:
- 1. Reason for Violation The subject pipe support was irtspected and accepted in accordance with the Hardware Validation Program (HVP) in May of 1987. Although our findings cannot be confirmed, TV Electric believes that the subject cotter pins may have been removed during painting activities which are known to have occurred subsequent to the HVP inspection and prior to the NRC inspectors observation of missing cotter pins.
- 2. Corrective Steps Taken and Results Achieved On August 26, 1987, Non-Conformance Report (NCR) 87-A01243 was written documenting the missing cotter pins. To determine the extent of the problem, a reinspection was initiated of 10'4 of the approximately 3000 pipe supports which had been inspected per the HVP. On September 4,1987, af ter reinspecting 45 pipe supports, a loose jam nut was found on pipe support CC-X-079-004-A43R. NCR 87-A01446 was written and the reinspection effort was terminated. Based on the identification of an additional discrepancy relating to configuration control. further sampling was not considered necessary and Corrective Action Request (CAR)87-075 was initiated.
Attachment to TXX-88450 :
May 16, 1988 Page 2 of 3 UPDATED RESPONSE TO VIOLATION ITEM C (445/8716-V-12) (Cont'd)
- 3. Corrective Steps Which Will be Taken to Avoid Further Violations On September 9, 1987, the Director of Construction directed that the missing / loose pipe support hardware be investigated and personnel retrained as required.
On September 14, 1987, the Director of Construction ordered that painting, insulating, and cleaning of safety related -; stems and components be stopped pending retraining of appropnate Construction Department personnel.
On September 15, 1987, Corrective Action Request (CAR)87-075 was issued to document the generic concerns raised by the discovery of the loose / missing hardware.
On September 18, 1987, following completion of the required training, the Work hold of September 14, 1987, was lifted.
On October 27, 1987, a training memo was issued for sign-off by all Comanche Peak Engineering personnel. This memo included instructions on the protection of permanent plant equipment, and was transmitted to all engineering contractors for training of their personnel.
On February 1, 1988, operations procedure STA-606, "Work Requests and Work Orders," was revised to require specific instructions for the removal and restoration of interferences.
On February 1, 1988, startup administrative procedures CP-SAP-13, "Temporary Modifications," and CP-SAP-6, "Control of Work on Station Components After Release from Construction to Startup," were revised to contain a cautionary statement indicating that only the work contained in the work documents is permitted.
On February 4, 1988, the Construction Department issued ECC Policy Statement No.2, "Maintaining Component Integrity," which emphasized the responsibility of individuals concerning component integrity.
On October 16, 1987, ramo NE-13371 from the Vice President of Engineering l and Construction was issued to engineering and construction personnel l reiterating the CPSES policy that all nuclear safety-related work must be performed in accordance with written engineering direction and approved procedures. Reading of this memo will be made part of our badging process.
Our 0A surveillance organization will incorporate observation of work in l l the area of pipe supports into their surveillance program. Field i l activities will be surveyed during the remainder of the construction phase ,
l to provide assurance that the activities being performed are within the i scope of the applicable work documents. The QA Surveillance program and personnel qualifications are governed by procedures NQA 3.23, "Surveillance Program," and NQA 1.16-4.01, "Indoctrination, Training and Qualification of QA Surveillance Personnel," respectively, i
l
.q ., o.
Attachment to TXX-88450 May 16, 1988 Page 3 of 3 Construction Procedure CP-CPM-7.1 "Package Flow Control" has been revised to require that work instructions contain specific direction to only perform those activities within the scope of the authorized documentation.
The requirements of procedure CP CPM-6.10. "Inspected Item Removal Form,"
have been revised and incorporated into new procedure ECC 2.13-5, "Construction Travelers," and ECC 2.13-5A Construction Traveler Generation" which will include appropriate guidance for working on or around accepted hardware.
The twelve CPE procedures that require personnel to enter Category I buildings ha~ve been revised to include cautionary statements regarding the alteration of installed and accepted equipment.
Painting Specifications 2323-AS-30 & 31 are being revised to include guidance for working on or around installed and accepted safety related equipment.
- 4. Date When Full Compliance W'll be Achieved Memo NE-13371 will be incorporated into our badging process no later than June 16, 1988.
The modification to our QA surveillance program described above will be completed no later than July 1, 1988.
The revisions to Specification 2323-AS-30 and 2323-AS-31 will be completed by June 16, 1988.
l l
l
.^
==
- """ """: Log # TXX-88460
=. .= File # 10130
- :: IR 87-31; 87-23 illELECTRIC IR Bl*35; Bl'26 Ref. # 10CFR2.201 I/,I,7,hN,","1, May 16, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 REVISED DATE OF FULL COMPLIANCE FOR NOTICE OF VIOLATION (N0V) ITEM A (445/8731-V-01)
AND NOV (445/8735-V-02)
REF: TV Electric letter Txx-88367 from W. G. Counsil to NRC dated March 31, 1988 Gentlemen:
The referenced letter provided our updated responses to NOV Item A (445/8731-V-01) and NOV (445/8735-V-02). In those responses we stated that by May 15, 1988, Ebasco walkdown procedures would be revised to minimize the need for personnel to measure to hypothetical lines such as conduit centerlines.
Revision of the applicable procedure has taken longer than expected.
Accordingly, our date for issuance of this revision is hereby revised to be no later than July 15, 1988.
Very truly yours, W. G. Counsil By.0AW- t~?. W -
idhn W. Beck Vice President, Nuclear Engineering RDD/grr c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 400 No,th Olne Str-
- ~
t EM 9 Log # TXX-88468
- = File # 10130 C C IR 88-20 1UELECTRIC IR 88*17 Ref. # 10CFR2.201 ISOIdE"1, May 23, 1988 V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 ,
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AhD 50-446 RESPONSE TO NRC INSPECTION REPORT N05.
50-445/88-20 AND 50-446/88-17 Gentlemen:
TV Electric has reviewed your letter dated April 22, 1988, concerning the inspection conducted by Mr. P. Stanish and other NRC consultants during the period March 2 through April 5,1988. This inspection covered activities authorized by NRC Construction Permits CPPR-126 and CPPR-127 for CPSES Units 1 and 2. Attached to your letter was a Notice of Violation.
On May 17, 1988, per a telephone conversation with Mr. R. F. Warnick, we requested and received an extension for NOV Item A (445/8820-V-01; 446/8817-V-01) until June 20, 1988.
We hereby respond to the balance of the Notice of Violation in the attachment to this letter.
Very truly yours, I,
W. G. Counsil L
RDD/grr Attachment c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 400 North Ohva Street LB 81 Dellas, Texas 1901
Attachment to TXX-88468 May 23, 1988 Page 1 of 5 NOTICE OF VIOLATION ITEM A (445/8820-V-01; 446/8817-V-01)
A. Criterion IX of Appendix B to 10 CFR Part 50, as implemented by Section 9.0, Revision 0, of the TV Electric Quality Assprance Manual, dated February 1,1988, requires the establishment of measures to assure that nondestructive testing is accomplished using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special reuqirements.
Contrary to the above, ultrasonic digital thickness measurements of site fabricated pipe bends to verify acceptable post-bend wall thickness, a Corrective Action Program commitmelit, were performed through protective coatings (primer and paint) without consideration of the impact of protective coatings on accuracy of measurements (445/8820-V-01; 446/8817-V-01).
RESPONSE TO NOTICE OF VIOLATION ITEM A (445/8820-V-01; 446/8817-V-01)
Response will be provided by June 20, 1988.
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. Attachment to TXX-88468 May 23, 1988 Page 2 of 5 NOTICE OF VIOLATION ITEM B (445/8820-V-02; 446/8817-V-02)
B. Criterion V of Appendix B to 10 CFR Part 50, as implemented by Section 5.0, Revision 0, of the TU Electric Quality Assurance Manual dated February 1, 1988, requires that activities affecting quality shall be prescribed by and accomplished in accordance with documented instructions, procedures, or driwings.
Brown and Root ASME Quality Procedure AQP-10.7, "Nondestructive Examination Marking Requirements," Revision 0, dated July 10, 1987, paragraph 1.3, approves the use of Nissen ink markers and Marsh stencil ink markers for temporary marking of stainless steel surfaces. No other ink markers are approved by this procedure.
Contrary to the above, while witnessing an ultrasonic digital thickness measurement inspection of a pipe bend on Spool 1Q3 of Piping Isometric BRP-WP-X-AB-041, the NRC inspector observed the QA inspector marking the stainless steel pipe surface with ballpoint pen ink, which is not an approved ink marker (445/8820-V-02; 446/8817-V-02).
RESPONSE TO NOTICE OF VIOLATION ITEM B (445/8820-V-02; 446/8817-V-02)
TV Electric agrees with the alleged' violation and the requested infonnation follows:
- 1. Reason for Violation The use of an unauthorized marker on stainless steel pipe during ultrasonic thickness (UT) measurement of the pipe bend noted in this violation resulted from QC inspector error. This conclusion is based upon discussions held with QC inspectors responsible for performing the UT measurements. We believe the use of an unauthorized marker was limited to one QC inspector.
- 2. Corrective Steps Taken and Results Achieved Nonconformance Report (NCR) 88-05684 was initiated to resolve the specific instance of unauthorized marker use noted in this violation.
l Additionally, one other instance of unauthorized marker use has been l
I identified and documented on NCR 88-05685. To confirm that unauthorized marker use was limited to one OC inspector, the disposition for Corrective Action Request (CAR)88-019 will require that all stainless
- steel pipe bends evaluated under the Post Construction Hardware l validation Program (PCHYP) prior to March 25, 1988, be inspected to verify that UT layout marks have been made using approved markers. If additional unauthorized marker use is identified, the area will be cleaned and "leachability" tests conducted in accordance with approved project procedures to assure acceptability. Stop Work Order (SWO)88-008 was issued on Mar:h 25, 1988, which stopped PCHVP UT examination of pipe bends pending resolution of UT method concerns. SWO 88-008 will be lif ted upon development of a satisfactory disposition to CAR 88-019.
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Attachment to.TXX-88468 May 23, 1988 Page 3 of 5
- 3. Corrective Steps Which Will be Taken to Avoid further Violations The actions taken as a result of CAR 88-019 will be sufficient to avoid further violations. The inspector responsible for use of improper marker is no longer onsite.
- 4. Date When Full Compliance Will be Achieved Full compliance will be achieved upon completion of the inspections required bf CAR 88-019 and disposition of NCRs 88-05684 and 88-05685.
These actions will be completed by August 20, 1988.
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Attachment to TXX-88468 May 23, 1988 Page 4 of 5 NOTICE OF VIOLATION ITEM C (445/8820-V-04)
C. Criterien X of Appendix B to 10 CFR Part 50, as implemented by Section 10.0, Revision 1, dated July 31, 1984, of the TV Electric Quality Assurance Plan, states, in part, "A program for inspection of activities affecting quality shall be established and executed . . . to verify conformance with the documented instructions, procedures, and drawings for accomptishing the pctivity."
Contrary to the above, the following conditions which had been inspected and accepted by the applicant's inspection programs were identified as being nonconforming during independent inspection of Unit I cable tray supports.
Section 3.2.2.8.2.a.1.d of TV Electric Field Verification Method THE-FVM-CS-001, Revision 5 dated July 1, 1986, states, in part, "Welding shall be verified for quantitative attributes as listed below without paint removed . . . weld size (to be measured)."
Section 3.2.2.B.2.2.>, states, in part, "A fillet weld shall be permitted to be less than the size specified by 1/16" for 1/4 (25'4) the length of the weld."
Section 1.5, "Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants," Revision 2 dated May 7, 1985 states: "The workmanship provisions of AWS D1.1 are not modified by the acceptance criteria presented in this document . . . ." Section 3.3.1 of AWS D1.1 dated 1975 states, in part, concerning ga as between members, ". . . if the separation is 1/16 inch or greater, tie leg of the fillet weld shall be increased by the amount of the separation or the contractor shall demonstrate that the effective throat has been obtained."
Section 4.1.2.2, "Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants," NCIG-01, Revision 2 dated May 7, 1985, states, in part, "A fillet weld shall be permitted to be less than the size specified by 1/16" for 1/4 the length of the weld."
Contrary to the above, independent inspection identified the following conditions in two supports:
- a. An 8" long, 5/16" fillet weld required by the drawing for a cable tray support was measured as being 1/4" for the full length,
- b. Two 6" long,1/4" fillet welds required by the drawing, for a cable tray support were measured as being 1/8" (due to an 1/8" gap between members) for the full length of both welds (445/8820-V-04).
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. Attachment to TXX-88468 May 23, 1988 Page 5 of 5 RESPONSE TO N0!!CE OF VIOLATION IIIFC7645/8820-V-04)
TV Electric agrees with the alleged violation and the requested information follows:
- 1. Reason for Violation The reason for this violation is attributed to limited QC inspector error. This conclusion is based upon review of QA Surveillance reinspection results. The ongoing QA Surveillance program performs overview reinspections of previously accepted checklist attributes to monitor the performance of QC inspection personnel. A review of Cable Tray Hanger (CTH) surveillance reinspection results indicated that neither of the QC inspectors involved had accepted any undersized welds in the samples examined - a total of 101 welding checklist attributes were reinspected for the two inspectors involved, 39 and 62, respectively. These results, along with the results of the NRC inspection noted in the details related to this violation, formed the basis for our conclusion.
- 2. Corrective Steps Taken and Results Achieved Nonconformance Reports (NCRs) 88-08411 and 88-08412 have been initiated to resolve the discrepancies. Although the NCRs have not been formally dispositioned, preliminary engineering review indicates the described conditions do not represent significant structural discrepancies.
- 3. Corrective Steps Which Will be Taken to Avoid Further Violations The QC inspectors who accepted the CTH welds described in the violation have been made aware of these errors. We believe this action to be sufficient to avoid further violations.
- 4. Date When Full Compliance Will be Achieved NCRs 88-08411 and 88-08412 will be dispositioned by August 20, 1988.
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F 7 Log # TXX-88470 m .= File # 10130 r C IR 87-31 TUELECTRIC g,g, , &cNg]ng pjli>3,
= G ynsl,j , May 20, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 .
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 REVISED DATE OF FULL COMPLIANCE FOR NOTICE OF VIOLATION (NOV)
ITEM B (445/8731-V-02; 446/8723-V-01)
REF: TV Electric letter TX7-88324 from W. G. Counsil to NRC dated March 18, 1988 Gentlemen:
The referenced letter provided our revised date of compliance to Notice of violation Item B (445/8731-V-02:446/8723-V-01), in that letter we stated that reinstruction to NE0 3.06 of engineering personnel responsible for NCR dispositions, and that closure of DRs C-88-00040, C-88-00041, and P-88-00054 would be completed by May 20, 1988. The subject DRs have been closed.
Reinstruction of engineering personnel has not been completed. Our date for completion of the reinstruction of engineering personnel is hereby revised to be no later than July 18, 1988.
Very truly yours,
- N W. G. Counsil ROD /grr 1
c-Mr. R. D. Martin, Region IV I Resident inspectors, CPSES (3) 400 North Ohn Street LBof Dallas. Toses 1H01
7 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION before the ATOMIC SAFETY AND LICENSING BOARD
- )
In the Matter of I) )
Docket Nos. 50-445-OL 50-446-OL TEXAS UTILITIES ELECTRIC )
COMPANY et al. )
) (Application for an (Comanche Peak Steam Electric ) Operating License)
Station, Units 1 and 2) )
)
CERTIFICATE OF SERVICE I, Thomas A. Schmutz, hereby certify that the foregoing letter was served this 6th day of June 1988, by mailing copies thereof (unless otherwise indicated),
l first class mail, postage prepaid to:
- Adjudicatory File (2 copies)
Chairman Atomic Safety and Licensing i Atomic Safety and Licensing Board Panel Docket Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Assistant Director for
- Alan S. Rosenthal, Esq. Inspection Programs Chairman Comanche Peak Project Division Atomic Safety and Licensing U.S. Nuclear Regulatory Appeal Panel Commission U.S. Nuclear Regulatory P.O. Box 1029 Commission Granbury, TX 76048 Washington, D.C. 20555 ,
- / Asterisk indicates service by hand or overnight courier.
2-
- ouanita Ellis Robert D. Martin President, CASE Regional Administrator, 1426 South Polk Street Region IV .
Dallas, TX 75224 U.S. Nuclear Regulatory
. Commission William R. Burchette, Esquire 611 Ryan' Plaza Drive Heron, Burchette, Ruckert, Suite 1000
& Rothwell Arlington, Texas 76011 Suite 700 l
1025 Thomas Jefferson St., N.W. Dr. Kenneth A. McCollom Washington, D.C. 20007 Administrative Judge 1107 West Knapp
- William L. Clements Stillwater, Oklahoma 74075 Docketing & Service Branch U.S. Nuclear Regulatory Joseph Gallo, Esquire j
Commission Hopkins & Sutter Washington, D.C. 20555 Suite 1250 1050 Connecticut Avenue, N.W.
- Billie Pirner Garde Washington, D.C. 20036 Government Accountability l Project *Janice E. Moore, Esquire Midwest Office Office of the General Counsel 104 E. Wisconsin Avenue - B U.S. Nuclear Regulatory Appleton, WI 54911-4897 Commission Washington, D.C. 20555 Susan M. Theisen, Esquire Assistant Attorney General
- Anthony Roisman, Esquire Attorney General of Texas 1401 New York Avenue, N.W.
Environmental Protection Division Suite 600 P.O. Box 12548 Washington, D.C. 20005 Austin, Texas 78711-1548 Lanny A. Sinkin Robert A. Jablon, Esquire Christic Institute Spiegel & McDiarmid 1324 North Capitol Street 1350 New York Avenue, N.W. Washington, D.C. 20002 l Washington, D.C. 20005-4798 Nancy Williams
- Elizabeth B. Johnson CYGNA Energy Services, Inc.
Oak Ridge National Laboratory 2121 N. California Blvd.
P.O. Box X Building 3500 Suite 390 Oak Ridge, Tennessee 37830 Walnut Creek, CA 94596
- Dr. Walter H. Jordan David R. Pigott 881 West Outer Drive Orrick, Herrington & Sutcliffe Oak Ridge, Tennessee 37830 600 Montgomery Street San Francisco, CA 94111
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- Robert A . Wooldridge, Esquire Worsham, Forsythe, Sampels
& Wooldridge 2001 Bryan Tower, Suite 3200 Dallas, Texas 75201
- W. G. Counsil Executive Vice President Texas Utilities Electric -
Generating Division 400 N. Olive, L.B. 81 Dallas, Texas 75201
/
lh Thomas A. Schmutz 6/
Dated: June 6, 1988 9
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